A physical tool for severe accident mitigation studies-Reference-Cited by-同舟云学术

A physical tool for severe accident mitigation studies

Published:2016-12 Issue: Volume:309 Page:224-235
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Marie N.,Bachrata A.,Seiler J.M.,Barjot F.,Marrel A.,Gossé S.,Bertrand F.

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference25 articles.

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2. Unprotected Loss of Flow simulation on ASTRID CFV V3 Reactor Core;Bachrata,2014

3. One component, volume heated, boiling pool Thermohydraulics;Bede,1993

4. Investigation of natural convection heat transfer to the cooled top boundary of a heated pool;Bernaz,1999

5. Comparison of the behaviour of two core designs for ASTRID in case of severe accidents;Bertrand;Nucl. Eng. Des. Nucl. Eng. Des.,2016

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